Mononitride Fuel for Fast Reactors

Substantiation is given for the development of nuclear power based on inherently-safe fast reactors with a mononitride core. Fundamental studies and design work on the development of such reactors with lead (BREST-OD-300), lead–bismuth (SVBR-75/100), and sodium coolant (BN-800) are being performed. The development of nuclear power in our country is based on organizing a closed fuel cycle. The results of experimental investigations of the properties of mononitride fuel are correlated. Mononitride fuel meets all requirements for fast-reactor fuel.

[1]  Kenneth L. Peddicord,et al.  Material property correlations for uranium mononitride , 1990 .

[2]  Kenneth L. Peddicord,et al.  Material property correlations for uranium mononitride: IV. Thermodynamic properties , 1990 .

[3]  Yasuo Arai,et al.  Thermophysical and thermodynamic properties of actinide mononitrides and their solid solutions , 1998 .

[4]  H. Blank,et al.  Basic aspects of swelling in dense livuid metal fast breeder reactor fuels , 1986 .

[5]  H. Matzke,et al.  Dense fuels in Europe , 1989 .

[6]  H. Blank,et al.  Specification and characterization of dense fuels for liquid metal cooled fast breeder reactors , 1988 .

[7]  Bruce J. Makenas,et al.  Fuels irradiation testing for the SP-100 program , 1991 .

[8]  Yu. E. Bagdasarov,et al.  Intrinsic Safety of Future BN-800 Based Nuclear Technology , 2001 .

[9]  V. W. Storhok,et al.  MIXED-NITRIDE FUEL IRRADIATION PERFORMANCE. , 1971 .

[10]  J. J. Laidler,et al.  Development of pyroprocessing technology , 1997 .

[11]  A. N. Holden.  High temperature nuclear fuels , 1968 .

[12]  H. Kleykamp.  Selection of materials as diluents for burning of plutonium fuels in nuclear reactors , 1999 .

[13]  Yasufumi Suzuki,et al.  Thermal conductivity of neptunium mononitride from 740 to 1600 K , 1994 .

[14]  H. Bernard.  Advanced fuel fabrication , 1989 .

[15]  C. Merlini,et al.  In-pile measurement of fission enhanced creep and swelling of uranium nitride , 1977 .

[16]  C. E. Till,et al.  Progress and status of the Integral Fast Reactor (IFR) fuel cycle development , 1993 .

[17]  Mohamed S. El-Genk,et al.  Thermal conductivity correlation for uranium nitride fuel between 10 and 1923 K , 1988 .

[18]  E. Storms.  An equation which describes fission gas release from UN reactor fuel , 1988 .

[19]  A. A. Bauer.  NITRIDE FUELS: PROPERTIES AND POTENTIALS. , 1972 .

[20]  C. Walker,et al.  Fission gas release and microscopic swelling in highly rated advanced fuels , 1980 .

[21]  P. V. Hegde,et al.  Preparation, characterisation and out-of-pile property evaluation of (U,Pu)N fuel pellets , 1991 .

[22]  D. Brucklacher,et al.  Creep behavior of ceramic nuclear fuels under neutron irradiation , 1972 .

[23]  R. L. Petty,et al.  Fabrication and testing of uranium nitride fuel for space power reactors , 1988 .

[24]  J. Routbort,et al.  Elastic, diffusional, and mechanical properties of carbide and nitride nuclear fuels — a review , 1975 .

[25]  Yasuo Arai,et al.  Fabrication of Uranium-Plutonium Mixed Nitride Fuel Pins for Irradiation Tests in JMTR , 1993 .